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Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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AI at work: Southern Nuclear’s adoption of Copilot agents drives fleet forward
Southern Nuclear is leading the charge in artificial intelligence integration, with employee-developed applications driving efficiencies in maintenance, operations, safety, and performance.
The tools span all roles within the company, with thousands of documented uses throughout the fleet, including improved maintenance efficiency, risk awareness in maintenance activities, and better-informed decision-making. The data-intensive process of preparing for and executing maintenance operations is streamlined by leveraging AI to put the right information at the fingertips for maintenance leaders, planners, schedulers, engineers, and technicians.
David A. Petti, Zoel R. Martinson, Richard R. Hobbins, Daniel J. Osetek
Nuclear Technology | Volume 94 | Number 3 | June 1991 | Pages 313-335
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A15812
Articles are hosted by Taylor and Francis Online.
Highly irradiated fuel rods and control rods are used in the Power Burst Facility Severe Fuel Damage (SFD) Test 1-4 to simulate conditions expected during a high-temperature, severe fuel damage accident in a pressurized water reactor. The objective of the test is to provide data on fuel and control rod behavior, hydrogen generation, and the release and transport of fission products and aerosols during severe accidents. Important results from the test based upon the response of on-line instrumentation, analysis of fission product and aerosol data, and postirradiation examination of the fuel bundle are presented. The results from SFD 1-4 provide insight into phenomena governing fuel bundle thermal response, Zircaloy oxidation and hydrogen generation, control rod degradation behavior, core melt progression, fission product release, aerosol generation, and fission product and aerosol deposition and transport.